KR900000324B1 - Steam generator of nuclear reactor - Google Patents

Steam generator of nuclear reactor Download PDF

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Publication number
KR900000324B1
KR900000324B1 KR1019850007254A KR850007254A KR900000324B1 KR 900000324 B1 KR900000324 B1 KR 900000324B1 KR 1019850007254 A KR1019850007254 A KR 1019850007254A KR 850007254 A KR850007254 A KR 850007254A KR 900000324 B1 KR900000324 B1 KR 900000324B1
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KR
South Korea
Prior art keywords
plug
steam generator
manhole
support arm
water chamber
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KR1019850007254A
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Korean (ko)
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KR860004432A (en
Inventor
이사오 시라스
Original Assignee
미쯔비시주우고오교오 가부시기가이샤
오다 테이시로오
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Publication of KR860004432A publication Critical patent/KR860004432A/en
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/02—Arrangements of auxiliary equipment
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/22—Drums; Headers; Accessories therefor
    • F22B37/221—Covers for drums, collectors, manholes or the like
    • F22B37/222—Nozzle dams introduced through a smaller manway, e.g. foldable
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G21C13/06—Sealing-plugs
    • G21C13/067—Sealing-plugs for tubes, e.g. standpipes; Locking devices for plugs
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Pressure Vessels And Lids Thereof (AREA)

Abstract

An isolating device for a vapor generator of the nuclear reactor of the type having a water chamber connected through a coolant pipe at its lower portion, and a nozzle section formed between the water chamber and the coolant pipe, comprises a support arm having an outer end mounted at a manhole section thereof and an inner end butted against an inner surface of the nozzle section, a plug which is pivotably attached to the forward end of the arm and is located within the nozzle section, and an angle adjusting screw which is intervened between the arm and the plug, the screw being constructed in a foldable manner.

Description

원자로용 증기발생기의 수실 격리장치Chamber isolation device for steam generator for nuclear reactor

제1도 내지 제7도는 본 발명의 실시예를 표시한 것으로서, 제1도는 수실 격리장치의 측면도.1 to 7 show an embodiment of the present invention, wherein FIG. 1 is a side view of a chamber isolation device.

제2a도는 시일덮개의 평면도.Figure 2a is a plan view of the seal cover.

제2b도는 제2a도의 b-b선에 따른 단면도.FIG. 2B is a cross-sectional view taken along the line b-b of FIG. 2A.

제3a도는 압압판의 평면도.3a is a plan view of the pressing plate.

제3b도는 제3a도의 b-b선에 따른 단면도.FIG. 3B is a cross-sectional view taken along the line b-b of FIG. 3A.

제4a도는 부착판과 지지아암의 조립상태를 표시한 평면도.4A is a plan view showing the assembling state of the attachment plate and the support arm.

제4b도는 제4a도의 b-b선에 따른 단면도.4b is a cross-sectional view taken along the line b-b of FIG. 4a.

제5a도는 시일덮개의 다른 변형예를 표시한 평면도.5A is a plan view showing another modification of the seal cover.

제5b도는 제5a도의 b-b선에 따른 단면도.FIG. 5B is a cross-sectional view taken along the line b-b of FIG. 5A.

제6도는 다른 형식의 플러그를 갖춘 수실 격리장치의 측면도.6 is a side view of a compartment isolation device with a plug of a different type.

제7a는 맨호울의 개폐기구를 표시한 단면도.Section 7a is a sectional view showing the opening and closing mechanism of the manhole.

제7b도는 제7a도의 b-b선에 따른 사시도.FIG. 7B is a perspective view along line b-b of FIG. 7A. FIG.

제8도는 가압수형 원자로의 개요를 표시한 계통도.8 is a schematic diagram showing an outline of a pressurized water reactor.

* 도면의 주요부분에 대한 부호의 설명* Explanation of symbols for main parts of the drawings

02 : 증기발생기 (02a) : 수실(水室)02: steam generator (02a): water chamber

(04) : 냉각재배관 (2) : 노즐부(04): Coolant pipe (2): Nozzle part

(25) : 맨호울 (3) : 부착자리(25): Manhole (3): Mounting seat

(8) : 지지아암 (10) : 각도조정나사(8): Supporting arm (10): Angle adjusting screw

(4) : 플러그 (26) : 커버(4): plug 26: cover

본 발명은, 원자로용 증기 발생기의 수실(水室)의 격리장치에 관한 것이다. 가압수형 원자로에 있어서는, 제8도에 표시한 바와 같이, 원자로용기(01)와, 증기 발생기(02)의 수실(02a)과, 냉각재펌프(03)는 냉각재배관(04)에 의해서 상호 연결되어 냉각재순환 루우프를 형성하고 있다.TECHNICAL FIELD This invention relates to the isolation | separation apparatus of the water chamber of the steam generator for nuclear reactors. In the pressurized water reactor, as shown in FIG. 8, the reactor vessel 01, the water chamber 02a of the steam generator 02, and the coolant pump 03 are connected to each other by the coolant piping 04. A coolant recycle loop is formed.

그리고, 원자력발전소에 있어서는, 그 구성기기, 계통의 안전성 확인 검사와 연료교환을 위하여 대략 1년에 1회 원자로의 운전이 정지된다.In the nuclear power plant, the reactor is stopped approximately once a year for safety confirmation and fuel exchange of the components and systems.

이 검사나 연료 교환에 있어서, 원자로 용기의 개방, 연료꺼냄, 노심 구조물의 점검, 연료의 장하(裝荷), 원자로의 재조립등의 원자로 관련의 작업은, 원자로용기(01) 및 원자로공동(公洞)(05) 등에 차폐수를 채우고, 이 수중에서 실시된다. 그리고, 이때 실시되는 증기발생기의 세관검사(細管檢査)는, 물을 뺀 상태에서 실시할 필요가 있으나, 원자로 관련의 작업시에는, 차폐수를 채우기 위해서 원자로 관련 작업과 증기발생기의 세관검사를 병행해서 실시할 수 없다. 따라서, 검사에 소요되는 시간이 길어져서 원자력발전소의 가동율 향상의 장해로 되어 있었다.In this inspection or fuel exchange, operations related to the reactor, such as opening the reactor vessel, removing fuel, inspecting the core structure, loading the fuel, and reassembling the reactor, are performed in the reactor vessel (01) and the reactor cavity ( A shielding water is filled in the same (05) and carried out in this water. In addition, although the customs inspection of a steam generator performed at this time needs to be performed in the state which drained water, in the case of reactor-related work, the reactor-related work and the customary inspection of a steam generator are performed simultaneously in order to fill a shielded water. It cannot be done. Therefore, the time required for inspection was long, which hindered the operation rate improvement of the nuclear power plant.

본 발명은, 상기를 감안하여, 증기 발생기의 수실을 원자로 냉각재배관, 원자로용기, 원자로공동등으로부터 격리하므로서, 증기발생기의 세관검사를 원자로 관련의 작업과 병행해서 실시가능케 하는 것이다.In view of the above, the present invention isolates the chamber of the steam generator from the reactor coolant piping, the reactor vessel, the reactor cavity, and the like, so that the customs inspection of the steam generator can be performed in parallel with the work related to the reactor.

본 발명에 의한 수실 격리장치는, 이 수실 맨호울부에 외단이 부착됨과 동시에 내단이 이 노즐부의 내면에 충접(衝接)한 지지아암, 이 지지아암의 선단부에 추착되어 이 노즐부내에 위치하는 플러그 및 이 플러그와 이 지지아암의 사이에 개장된 각도 조정나사를 가지고, 이 플러그를 접어갤 수 있도록 구성하고 있다.In the chamber isolation device according to the present invention, a support arm having an outer end attached to the chamber manhole part and having an inner end abutted on an inner surface of the nozzle part, and a plug which is struck in the tip end of the support arm and positioned in the nozzle part And an angle adjusting screw inserted between the plug and the support arm to fold the plug.

이하, 본 발명의 실시예인 수실 격리장치(50)를 참조하면서, 구체적으로 설명한다.Hereinafter, with reference to the water chamber isolation device 50 which is an embodiment of the present invention, it will be described in detail.

제1도에 있어서, 원자로용기에 냉각재배관을 개재해서 연락한 증기발생기의 수실(1)은, 냉각재배관의 노즐부(2)에 연락하고, 수실(1)로 통하는 맨호울(25)에 덮개(도시하지 않음)의 부착자리(3)가 형성되어 있다. 노즐부(2)의 내부에 배치되는 플러그(4)는, 시일덮개(5), 압압판(6), 부착판(7) 등으로 이루어지며, 수실 격리장치(50)의 주요부를 차지한다. 지지아암(8)은, 그 일단이 맨호울의 부착자리(3)에 볼트(9)로 착탈자재하게 고정되고, 타단은 노즐부(2)의 내벽에 계지되어 있다. 지지아암(8)과 부착판(7)과의 사이에 개장된 각도 조정나사(10)에 의해, 플러그(4)의 자세를 호적하게 유지한다. 시일덮개(5)는, 제2도(a)(b)에 표시된 바와 같이, 맨호울(25)로부터 수실(1)내로 반입하기 위하여 힌지(11)에 의해 파선으로 표시한 바와 같이 셋으로 접기가 가능하고, 또한 그 하면 및 상면에는 고무판(13)이 각각 붙어있다. 또 압압판(6) 및 부착판(7)에 일체적으로 죄어 결합시키기 위한 4개의 볼트(14)가 식설되어 있다. 압압판(6)은 제3도(a)(b)에 표시한 바와 같이 노즐부(2)보다 작은 맨호울(25)로부터 수실(1)내에 반입하기 위하여 2분할 되고, 또한, 위치결정을 용이하게 하기 위하여 볼트(14)가 관통하는 버섯형상의 볼트 구멍(15)을 갖추고 있다. 부착판(7)은, 제4도(a)(b)에 표시한 바와 같이 그 일단상면에 돌설된 브래킷(16)을 구비하고, 이 브래킷(16)은 핀(17)에 의해 지지아암(8)의 단부하면에 돌설된 브래킷(18)과 추지(樞支)된다. 그리고, 부착판(7)의 상면중앙부에 고착된 자리(19)에는, 각도조정나사(10)의 하단에 형성된 구(球)(20)가 절구운동이 가능토록 감합되어 있다. 각도 조정나사(10)는, 지지아암(8)에 활동회동 가능하도록 지지된 원통형상핀(21)의 나사구멍(22)과 나합해서 관통하여, 위쪽으로 뻗어 그 상단에는 4각면(23)이 형성되어 있다. 부착판(7)에도 위치결정을 용이하게 하기 위하여 볼트(14)가 관통하는 버섯형상의 볼트구멍(24)이 형성되어 있다.In FIG. 1, the water chamber 1 of the steam generator in contact with the reactor vessel via the coolant pipe is in contact with the nozzle portion 2 of the coolant pipe and covers the manhole 25 leading to the water chamber 1. An attachment seat 3 (not shown) is formed. The plug 4 disposed inside the nozzle portion 2 is composed of a seal cover 5, a press plate 6, an attachment plate 7, and the like, and occupies a main portion of the chamber isolation device 50. One end of the support arm 8 is detachably fixed to the attachment position 3 of the manhole with a bolt 9, and the other end thereof is locked to the inner wall of the nozzle portion 2. The attitude | position of the plug 4 is hold | maintained suitably by the angle adjusting screw 10 installed between the support arm 8 and the attachment plate 7. As shown in FIG. The seal lid 5 is folded in three as indicated by dashed lines by the hinge 11 for carrying in from the manhole 25 into the water chamber 1, as shown in FIG. 2 (a) (b). The rubber plate 13 is attached to the lower surface and the upper surface, respectively. In addition, four bolts 14 are integrally fastened to the pressing plate 6 and the attachment plate 7. The pressing plate 6 is divided into two in order to carry into the water chamber 1 from the manhole 25 smaller than the nozzle part 2, as shown to FIG. 3 (a) (b), and further, positioning is carried out. The mushroom bolt hole 15 through which the bolt 14 penetrates is provided for the ease. The attachment plate 7 is provided with the bracket 16 which protruded in the upper end surface as shown to FIG. 4 (a) (b), and this bracket 16 is supported by the pin 17 by the support arm ( It is pointed out with the bracket 18 which protruded on the lower end surface of 8). In the seat 19 fixed to the center of the upper surface of the attachment plate 7, a ball 20 formed at the lower end of the angle adjusting screw 10 is fitted to allow the mortar motion. The angle adjusting screw 10 passes through the screw hole 22 of the cylindrical pin 21 supported by the support arm 8 so as to be rotatable, extends upward, and forms a quadrilateral surface 23 at the upper end thereof. It is. The attachment plate 7 is also provided with a mushroom-shaped bolt hole 24 through which the bolt 14 penetrates in order to facilitate positioning.

그리하여, 증기 발생기를 포함한 냉각재순환 루우프가 배수가 되고, 맨호울(25)이 개방된 상태에 있어서, 수실 격리장치(50)가 부착된다. 즉 시일덮개(5)를 셋으로 접어개어서 맨호울(25)로부터, 수실(1)내에 반입한 후, 수실(1)내에서 판형상으로 전개한다. 이어서 압압판(6)을 분할된 상태로 맨호울(25)로부터 수실(1)내에 반입한다. 또 부착판(7)과 지지아암(8)을 제4도에 표시한 조립상태로 맨호울(25)로부터 수실(1)내에 반입한다. 그래서 시일덮개(5)의 위에 압압판(6)을 포개고, 또 그 위에 부착판(7)을 포개어 볼트(14)를 버섯형상의 볼트구멍(15)(24)을 관통시켜서 위치 결정하고, 볼트(14)의 상단에 너트(26)를 나입하여 죄므로서 플러그(4)를 조립한다. 이어서, 각도조정나사(10)를 그 상단에 형성된 4각면(23)에 스패너 등을 대어 회전시키면, 플러그(4)는 핀(17)의 주위에 회전하여, 지지아암(8)에 대해서 소정의 각도를 이룬다. 그래서, 플러그(4)를 노즐부(2)내에 끼워넣어, 지지아암(8)의 선단을 노즐부(2)의 내면에 계지(係止)시킨 상태에서 지지아암(8)의 기단(基端)을 볼트(9)에 의해 맨호울(25)의 부착자리(3)에 고정한다. 이리하여, 노즐부(2)의 플러그(4)에 의한 폐색이 완료된다. 또한, 시일덮개(5)는 제5도(a)(b)에 표시한 바와 같이 2분할하여, 그 하면에 붙인 고무판(12)에 의해 연결해서 도면의 파선으로 표시한 바와 같이 둘로 접을 수 있도록 해도 좋다. 또, 제6도에 표시한 바와 같이, 압압판(6)을 생략할 수도 있다.Thus, the coolant circulation loop including the steam generator is drained, and the water chamber isolator 50 is attached in the state where the manhole 25 is opened. That is, the seal cover 5 is folded in three, carried in from the manhole 25 into the water chamber 1, and is developed in the water chamber 1 in plate shape. Next, the press plate 6 is carried in from the manhole 25 into the water chamber 1 in the divided state. Moreover, the attachment plate 7 and the support arm 8 are carried in from the manhole 25 into the water chamber 1 in the assembled state shown in FIG. Then, the pressing plate 6 is stacked on the seal cover 5, and the attachment plate 7 is stacked thereon to position the bolts 14 through the mushroom-shaped bolt holes 15 and 24, thereby positioning the bolts. The plug 4 is assembled by inserting the nut 26 at the upper end of the 14 and tightening it. Subsequently, when the angle adjusting screw 10 is rotated by applying a spanner or the like to the quadrilateral surface 23 formed at the upper end thereof, the plug 4 is rotated around the pin 17 so as to be predetermined with respect to the support arm 8. Make an angle. Thus, the base 4 of the support arm 8 is inserted in the state where the plug 4 is inserted into the nozzle unit 2 and the tip of the support arm 8 is locked to the inner surface of the nozzle unit 2. ) Is fixed to the attachment seat 3 of the manhole 25 by bolts 9. In this way, the blockage by the plug 4 of the nozzle part 2 is completed. In addition, the seal cover 5 is divided into two as shown in Fig. 5 (a) and (b), and connected by a rubber plate 12 attached to the lower surface thereof so that the seal cover 5 can be folded in two as indicated by the broken line in the drawing. You may also In addition, as shown in FIG. 6, the press plate 6 can also be abbreviate | omitted.

그리하여, 노즐부(2)의 플러그(4)에 의한 폐색이 완료되면, 원자로공동(05)내에 물을 주입한다. 그러면 냉각배관(04)을 개재해서 물이 노즐부(2)에 도달하여, 플러그(4)의 하면에 1kg/㎠의 수압이 작용하고, 시일덮개(5)의 하면에 붙어 있는 고무판(12)이 노즐부(2)의 내면에 압착되어서 시일됨과 동시에 이 수압에 의해서 플러그(4)에 부하되는 힘은 지지아암(8)의 선단을 개재해서 노즐부(2)의 내면에 의해서 지지된다.Thus, when the blockage by the plug 4 of the nozzle unit 2 is completed, water is injected into the reactor cavity 05. Then, water reaches the nozzle part 2 via the cooling pipe 04, and a 1 kg / cm <2> hydraulic pressure acts on the lower surface of the plug 4, and the rubber plate 12 adheres to the lower surface of the seal cover 5. The force applied to the plug 4 by being pressed against the inner surface of the nozzle part 2 and loaded by the hydraulic pressure is supported by the inner surface of the nozzle part 2 via the tip of the support arm 8.

이리하여, 증기발생기는, 다른 1차 냉각계통과 격리되므로, 이 상태에서 증기발생기의 세관검사를 로보트 등에 의해 실시하고, 이 세관검사와 병행해서 원자로 관련의 정기검사 작업을 실시할 수 있다.Thus, since the steam generator is isolated from other primary cooling systems, the customs inspection of the steam generator can be performed by a robot or the like in this state, and the periodic inspection work related to the reactor can be carried out in parallel with the customs inspection.

노즐부(2)에 착설한 플러그(4)로부터의 만일의 누수를 방지하기 위하여, 제7도(a)(b)에 표시한 바와 같이 맨호울(25)은 커버(26)로 폐색된다. 커버(26)는 한지(27) 주위에 회동가능하게 자리판(28)에 연결되며, 자리판(28)은 맨호울(25)의 부착자리(3)에 볼트(29) 및 너트(30)에 의해 죄어진다. 볼트(29)주위에 회전가능하게 부착된 레버(31)를 화살표방향으로 회동하므로서, 레버(31)의 선단이 커버(26)의 중간높이의 외표면에 당접하여, 커버(26)는 자리판(28)에 밀착되게 된다. (32)는 커버(26)의 외표면에 착설한 손잡이, (33)은 증기 발생기의 세관검사 및 보수용의 로봇, (34)는 로봇(33)를 제어하기 위한 케이블로서 커버(26)의 중앙에 천설한 시일(35)을 관통해서 외부로 뻗어있다. 증기 발생기의 세관검사 및 그 보수시에는 커버(26)는 제7도(a)의 파선으로 표시한 상태로하여 맨호울(25)을 개방하여두나, 만일 플러그(4)로부터의 누수가 있을 때는 손잡이(32)를 잡고, 커버(26)을 한지(27)주위에 회동하므로서 맨호울(25)을 폐색하고, 레버(31)를 볼트(29)주위에 화살표 방향으로 회동시키므로서 자리판(28)에 밀착시켜, 플러그(4)로부터의 누수가 맨호울(25)로부터 유출하는 것을 억지한다.In order to prevent accidental leakage from the plug 4 installed on the nozzle part 2, the manhole 25 is closed by the cover 26, as shown in FIG. 7 (a) (b). The cover 26 is rotatably connected to the seat plate 28 around the paper 27, and the seat plate 28 is connected to the seat 3 of the manhole 25 with the bolt 29 and the nut 30. Squeezed by By rotating the lever 31 rotatably attached around the bolt 29 in the direction of the arrow, the tip of the lever 31 abuts the outer surface of the intermediate height of the cover 26, so that the cover 26 is a seat plate. It comes in close contact with (28). Reference numeral 32 denotes a handle installed on the outer surface of the cover 26, 33 a robot for customs inspection and repair of the steam generator, and 34 a cable for controlling the robot 33 as a cable for controlling the robot 26. It extends through the seal 35 laid in the center and to the outside. During customs inspection and maintenance of the steam generator, the cover 26 is opened with the broken line in FIG. 7 (a), and the manhole 25 is opened, but if there is a leak from the plug 4 Holding the handle 32, the manhole 25 is closed by turning the cover 26 around the paper 27, and the seat plate 28 by rotating the lever 31 in the direction of the arrow around the bolt 29. ), The leakage from the plug 4 is prevented from flowing out of the manhole (25).

본 발명에 있어서는 가압수형 원자로의 증기발생기의 수실로 통하는 냉각재배관의 노즐부에 플러그를 착설함과 동시에 상기 수실로 통하는 맨호울의 부착자리에 고정되고 각도조정나사를 착설한 지지아암에 의해서 상기 플러그를 지지하고, 또한, 상기 맨호울의 부착자리에 커버를 착설하였으므로, 증기 발생기의 수실로 통하는 냉각재배관의 노즐부를 플러그에 의해서 폐색하여, 증기 발생기를 다른 1차 냉각계통으로 격리할 수 있다. 따라서, 증기발생기의 세관검사 및 보수와 원자로 관련의 정기검사 작업을 동시에 병행해서 실시할 수 있으므로, 정기검사 기간을 단축할 수 있고, 방사선 피복(被曝)의 저감과 원자력발전소의 가동율 향상에 이바지 할 수 있다. 또, 플러그 맨호울의 부착자리에 고정한 지지아암에 각도조정나사를 사용해서 소정의 자세로 지지되며, 플러그에 부하되는 수압은 지지아암을 개재해서 증기 발생기에 의해서 부담되므로 특별한 지지가구를 필요로 하지 않는다. 또 맨호울의 부착자리에 커버를 착설하므로서, 플러그로부터 만일 누수해도 이 물이 맨호울로부터 유출하는 것을 억지할 수 있다.In the present invention, the plug is installed on the nozzle portion of the coolant pipe leading to the water chamber of the steam generator of the pressurized water reactor, and is fixed to the attachment position of the manhole to the water chamber, and is supported by the support arm on which the angle adjusting screw is installed. Since the cover is installed at the attachment position of the manhole, the nozzle part of the coolant pipe leading to the water chamber of the steam generator can be closed by a plug to isolate the steam generator from another primary cooling system. Therefore, the customs inspection and repair of the steam generator and the regular inspection work related to the reactor can be carried out at the same time, so that the periodic inspection period can be shortened, which contributes to the reduction of the radiation coating and the improvement of the operation rate of the nuclear power plant. Can be. In addition, the support arm fixed to the mounting position of the plug manhole is supported by a predetermined posture using an angle adjusting screw. The hydraulic pressure applied to the plug is burdened by the steam generator through the support arm, so no special support furniture is required. Do not. In addition, by installing the cover at the attachment position of the manhole, even if water leaks from the plug, this water can be prevented from flowing out of the manhole.

Claims (1)

원자로용기에 냉각재배관을 개재해서 연통한 수실을 하부에 가지며, 이 수실과 이 냉각재배관과의 사이에 노즐부가 형성된 원자로용 증기발생기의 수실 격리장치로서, 이 수실의 맨호울부에 외단이 부착됨과 동시에 내단이 이 노즐부의 내면에 충접한 지지아암, 이 지지아암의 선단부에 추착되고 이 노즐부내에 위치하는 플러그 및 이 플러그와 이 지지아암의 사이에 개장된 각도조정나사를 가지고, 이 플러그를 접어갤 수 있도록 구성하고 있는 것을 특징으로 하는 원자로용 증기 발생기의 수실 격리장치.A water chamber isolation device of a steam generator for a nuclear reactor having a nozzle portion connected to a reactor vessel via a coolant pipe via a coolant pipe at a lower portion thereof, wherein the outer end is attached to the manhole of the water chamber. The plug has a support arm whose inner end is in contact with the inner surface of the nozzle portion, a plug which is squeezed into the tip of the support arm and is located in the nozzle portion, and an angle adjusting screw inserted between the plug and the support arm. A chamber isolation device for a steam generator for a nuclear reactor, characterized in that configured to allow
KR1019850007254A 1984-11-15 1985-10-02 Steam generator of nuclear reactor KR900000324B1 (en)

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Also Published As

Publication number Publication date
FR2573237A1 (en) 1986-05-16
KR860004432A (en) 1986-06-23
FR2573237B1 (en) 1991-12-06
JPH0238164Y2 (en) 1990-10-16
JPS6189604U (en) 1986-06-11
US4777008A (en) 1988-10-11

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